Affiliation:
1. 1VUJE, Inc., Okružná 5, 918 64 Trnava, Slovakia
Abstract
AbstractVVER-440 reactors have been utilized in Slovakia since 1978. So far, the vast majority of their core loadings were designed in VUJE institute. This paper presents a description of the methods and procedures, which have been used for this purpose in the last decade. Main attention is focused on the calculating tools for core refuelling scheme optimization.
Subject
Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation
Reference4 articles.
1. BIPR-7 code, Algorithm description and user manual. (in Russian) RNC “Kurchatovskiy institut”, Moscow, 1995
2. Pressurized Water Reactor Optimal Core Management and Reactivity Profiles
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1 articles.
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